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1
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0023293299
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Corrosion assisted cracking of stainless and low alloy steels in lwr environments
-
February
-
F.P. Ford, D.F. Taylor, P.L. Andresen and R.G. Ballinger, "Corrosion Assisted Cracking of Stainless and Low Alloy Steels in LWR Environments", EPRI Contract RP2006-6, Report NP5064M, February 1987.
-
(1987)
EPRI Contract RP2006-6, Report NP5064M
-
-
Ford, F.P.1
Taylor, D.F.2
Andresen, P.L.3
Ballinger, R.G.4
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2
-
-
0002139532
-
Development and use of a predictive model of crack propagation in 304/316l, a533b/a508 and inconel 600/182 in 288°c Water
-
TMS
-
F.P. Ford and P.L. Andresen, "Development and Use of a Predictive Model of Crack Propagation in 304/316L, A533B/A508 and Inconel 600/182 in 288°C Water", Third Int. Symp. on Degradation of Materials in Nuclear Power Systems - Water Reactors, TMS, pp.789-800, 1988.
-
(1988)
Third Int. Symp. on Degradation of Materials in Nuclear Power Systems - Water Reactors
, pp. 789-800
-
-
Ford, F.P.1
Andresen, P.L.2
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3
-
-
0024054216
-
Life prediction by mechanistic modelling and system monitoring of environmental cracking of fe and ni alloys in aqueous Systems
-
P.L. Andresen and F.P. Ford, "Life Prediction by Mechanistic Modelling and System Monitoring of Environmental Cracking of Fe and Ni Alloys in Aqueous Systems", Materials Science and Engineering, A103, pp.167-183, 1988.
-
(1988)
Materials Science and Engineering
, vol.A103
, pp. 167-183
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-
Andresen, P.L.1
Ford, F.P.2
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4
-
-
1942435611
-
Application of water chemistry control, on-line monitoring and crack growth rate models for improved bwr materials Performance
-
NACE 4-51
-
F.P. Ford, P.L. Andresen, HD. Solomon, G.M. Gordon, S. Ranganath, D. Weinstein, and R. Pathania, "Application of Water Chemistry Control, On-Line Monitoring and Crack Growth Rate Models for Improved BWR Materials Performance", Fourth Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, NACE, pp.4-26 to 4-51, 1990.
-
(1990)
Fourth Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors
, pp. 4-26
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-
Ford, F.P.1
Andresen, P.L.2
Solomon, H.D.3
Gordon, G.M.4
Ranganath, S.5
Weinstein, D.6
Pathania, R.7
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5
-
-
0002585992
-
Corrosion in nuclear systems: Environmentally assisted cracking in light water reactors
-
Ed. P. Marcus and J. Ouder, Marcel Dekker
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F.P. Ford and P.L. Andresen, "Corrosion in Nuclear Systems: Environmentally Assisted Cracking in Light Water Reactors", in "Corrosion Mechanisms", Ed. P. Marcus and J. Ouder, Marcel Dekker, p.501-546, 1994.
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(1994)
Corrosion Mechanisms
, pp. 501-546
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-
Ford, F.P.1
Andresen, P.L.2
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6
-
-
0027929646
-
Fundamental modeling of environmental cracking for improved design and lifetime evaluation in bwrs
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P.L. Andresen and F.P. Ford, "Fundamental Modeling of Environmental Cracking For Improved Design and Lifetime Evaluation in BWRs", Int. J. of Pressure Vessel and Piping 59, 1994.
-
(1994)
Int. J. of Pressure Vessel and Piping
, vol.59
-
-
Andresen, P.L.1
Ford, F.P.2
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7
-
-
4243157830
-
-
Paper #495, Corrosion/90, NACE
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P.L. Andresen, I.P. Vasatis & F.P. Ford, "Behavior of Short Cracks in Stainless Steel at 288°C", Paper #495, Corrosion/90, NACE, 1990.
-
(1990)
Behavior of Short Cracks in Stainless Steel at 288°C
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-
Andresen, P.L.1
Vasatis, I.P.2
Ford, F.P.3
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8
-
-
0004184893
-
Irradiation assisted stress corrosion cracking
-
Book on Ed. R.H. Jones, ASM, Materials Park
-
P.L. Andresen, "Irradiation Assisted Stress Corrosion Cracking", in Book on Stress Corrosion Cracking: Materials Performance and Evaluation, Ed. R.H. Jones, ASM, Materials Park, 1992, p.181-210.
-
(1992)
Stress Corrosion Cracking: Materials Performance and Evaluation
, pp. 181-210
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-
Andresen, P.L.1
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9
-
-
85046765688
-
Fracture mechanics data and modeling of environmental cracking of nickel alloys in high temperature water
-
Germany
-
P.L. Andresen, "Fracture Mechanics Data and Modeling of Environmental Cracking of Nickel Alloys in High Temperature Water", VGB Conference on Corrosion and Corrosion Protection in Power Plants, Germany, 1995.
-
(1995)
VGB Conference on Corrosion and Corrosion Protection in Power Plants
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-
Andresen, P.L.1
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15
-
-
0009492404
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SCC of low alloy steels in high temperature water
-
ANS
-
F.P. Ford, P.L. Andresen, D. Weinstein & S. Ranganath, "SCC of Low Alloy Steels in High Temperature Water", Proc. Fifth Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, ANS, pp.561-570, 1991.
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(1991)
Proc. Fifth Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors
, pp. 561-570
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-
Ford, F.P.1
Andresen, P.L.2
Weinstein, D.3
Ranganath, S.4
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16
-
-
0009548775
-
Corrosion fatigue of a533b/a508 pressure vessel steels in water at 288°c
-
Moscow, USSR, May 1990, NRC NUREG/CP-0112 (ANL-90/22
-
F.P. Ford and P.L. Andresen, "Corrosion Fatigue of A533B/A508 Pressure Vessel Steels in Water at 288°C", Proc. Third Intl. Atomic Energy Agency Specialists Mtg on Subcriticai Crack Growth, Moscow, USSR, May 1990, NRC NUREG/CP-0112 (ANL-90/22), Vol. 1, p. 105-124.
-
Proc. Third Intl. Atomic Energy Agency Specialists Mtg on Subcriticai Crack Growth
, vol.1
, pp. 105-124
-
-
Ford, F.P.1
Andresen, P.L.2
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17
-
-
0347229302
-
Stress corrosion cracking of a533b/pressure vessel steels in water at 288°c
-
Moscow, USSR, May 1990, NRC NUREG/CP-0112 (ANL-90/22
-
F.P. Ford and P.L. Andresen, "Stress Corrosion Cracking of A533B/Pressure Vessel Steels in Water at 288°C", Third Inter. Atomic Energy Agency Specialists Mtg on Subcriticai Crack Growth, Moscow, USSR, May 1990, NRC NUREG/CP-0112 (ANL-90/22), Vol. 2, p.37-54.
-
Third Inter. Atomic Energy Agency Specialists Mtg on Subcriticai Crack Growth
, vol.2
, pp. 37-54
-
-
Ford, F.P.1
Andresen, P.L.2
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18
-
-
0348049191
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-
Paper #44, Corrosion/91, NACE Houston, March
-
P.L. Andresen, "Fracture Mechanics Data & Modeling of Environmental Cracking of Nickel-Base Alloys in High Temperature Water", Paper #44, Corrosion/91, NACE, Houston, March 1991.
-
(1991)
Fracture Mechanics Data & Modeling of Environmental Cracking of Nickel-Base Alloys in High Temperature Water
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-
Andresen, P.L.1
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19
-
-
85046711752
-
Development of data and predictive models for environmental cracking of nickel alloys in 288°c water
-
May
-
P.L. Andresen, "Development of Data and Predictive Models for Environmental Cracking of Nickel Alloys in 288°C Water", Final Report on EPRI Contract RP2006-17, May 1991.
-
(1991)
Final Report on EPRI Contract RP2006-17
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-
Andresen, P.L.1
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20
-
-
0000534797
-
Characterization of the roles of electrochemistry, convection and crack chemistry in stress corrosion cracking
-
NACE
-
P.L. Andresen and L.M. Young, "Characterization of the Roles of Electrochemistry, Convection and Crack Chemistry in Stress Corrosion Cracking", Proc. Seventh Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, NACE, p.579-596, 1995.
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(1995)
Proc. Seventh Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors
, pp. 579-596
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-
Andresen, P.L.1
Young, L.M.2
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22
-
-
0001244793
-
The solubility of magnetite and the hydrolysis and oxidation of fe2+ in water to 300°c
-
P.R. Tremarne and J.C. LeBlanc, "The Solubility of Magnetite and the Hydrolysis and Oxidation of Fe2+ in Water to 300°C", J Soin Chem 9, 6, p.415-442, 1980.
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(1980)
J Soin Chem
, vol.9
, Issue.6
, pp. 415-442
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Tremarne, P.R.1
LeBlanc, J.C.2
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23
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-
0005279680
-
The solubility of nickel oxide and hydrolysis and oxidation of ni2+ in water to 573°ak
-
P.R. Tremaine and J.C. LeBlanc, "The Solubility of Nickel Oxide and Hydrolysis and Oxidation of Ni2+ in Water to 573°aK", J Chem Thermodynamics 12, 16, p.521-538, 1980.
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(1980)
J Chem Thermodynamics
, vol.12
, Issue.16
, pp. 521-538
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Tremaine, P.R.1
LeBlanc, J.C.2
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24
-
-
0642343341
-
Effect of sulfur on the protective layers of alloys 600 and 690 in low and high temperature environments
-
NACE, 5-79
-
P. Combrade, M. Foucault, P. Marcus, J.-M. Grimal, and A. Gelpi, "Effect of Sulfur on the Protective Layers of Alloys 600 and 690 in Low and High Temperature Environments", Proc. Fourth Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, NACE, pp.5-79 to 5-95, 1990.
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(1990)
Proc. Fourth Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors
, pp. 5-95
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-
Combrade, P.1
Foucault, M.2
Marcus, P.3
Grimal, J.-M.4
Gelpi, A.5
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25
-
-
0343856632
-
On the role of sulfur on the dissolution of pressure vessel steels at the tip of a propagating crack in pwr environment
-
NACE, 8-48
-
P. Combrade, M. Foucault, P. Marcus, G. Slama, "On the Role of Sulfur on the Dissolution of Pressure Vessel Steels at the Tip of a Propagating Crack in PWR Environment", Proc. Fourth Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, NACE, pp.8-48 to 8-63, 1990.
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(1990)
Proc. Fourth Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors
, pp. 8-63
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-
Combrade, P.1
Foucault, M.2
Marcus, P.3
Slama, G.4
-
26
-
-
33745908991
-
Computer simulation of environmentally assisted cracking of rpv steels in lwr environments
-
NACE, 8-28
-
T. Shoji, S. Moriya and M. Tada, "Computer Simulation of Environmentally Assisted Cracking of RPV Steels in LWR Environments", Proc. Fourth Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, NACE, pp.8-28 to 8-47, 1990.
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(1990)
Proc. Fourth Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors
, pp. 8-47
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-
Shoji, T.1
Moriya, S.2
Tada, M.3
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27
-
-
85046787050
-
An integrated approach to investigating scc
-
April
-
B.W. Bussen, I. Goldberg, R.F. Keefer, and N. Lewis, "An Integrated Approach to Investigating SCC", Workshop on PWSCC of Alloy 600 in PWRs, EPRI, April 1993.
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(1993)
Workshop on PWSCC of Alloy 600 in PWRs, EPRI
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-
Bussen, B.W.1
Goldberg, I.2
Keefer, R.F.3
Lewis, N.4
-
28
-
-
51249166985
-
Creep and intergranular cracking of ni-cr-fe alloys in argon at 360°c
-
T.M. Angeliu and G.S. Was, "Creep and Intergranular Cracking of Ni-Cr-Fe Alloys in Argon at 360°C", Met. Trans, 25 A, p. 1169-1184, 1994.
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(1994)
Met. Trans, 25 A
, pp. 1169-1184
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-
Angeliu, T.M.1
Was, G.S.2
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31
-
-
85046819396
-
-
Paper 96086, Corrosion/96, NACE
-
T.M. Angeliu, P.L. Andresen, and M.L. Pollick "Repassivation and Crack Propagation of Alloy 600 in 288°C Water", Paper 96086, Corrosion/96, NACE, 1996.
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(1996)
Repassivation and Crack Propagation of Alloy 600 in 288°C Water
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-
Angeliu, T.M.1
Andresen, P.L.2
Pollick, M.L.3
-
33
-
-
85031523604
-
Analysis of a600 and x-750 scc cracks
-
Arlie, VA, EPRI, Palo Alto, April 6-9
-
CD. Thompson, N. Lewis, and H.T. Krasodomski, "Analysis of A600 and X-750 SCC Cracks", Alloy 600 Experts Meeting, Arlie, VA, EPRI, Palo Alto, April 6-9, 1993.
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(1993)
Alloy 600 Experts Meeting
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-
Thompson, C.D.1
Lewis, N.2
Krasodomski, H.T.3
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34
-
-
0343585575
-
Prediction of pwscc in nickel base alloys using crack growth models
-
NACE
-
CD. Thompson, H.T. Krasodomski, N. Lewis, and G.L. Makar, "Prediction of PWSCC in Nickel Base Alloys Using Crack Growth Models", Proc. Seventh Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, NACE, p.867-880, 1995.
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(1995)
Proc. Seventh Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors
, pp. 867-880
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Thompson, C.D.1
Krasodomski, H.T.2
Lewis, N.3
Makar, G.L.4
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35
-
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0343585589
-
Alloy 600 scc growth measurements in primary coolant
-
November
-
D.M. Carey, D.J. Perry, T.R. Miller and CD. Thompson, "Alloy 600 SCC Growth Measurements in Primary Coolant", Workshop on PWSCC of Alloy 600 in PWRs, EPRI, November 1994.
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(1994)
Workshop on PWSCC of Alloy 600 in PWRs, EPRI
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-
Carey, D.M.1
Perry, D.J.2
Miller, T.R.3
Thompson, C.D.4
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41
-
-
33745216318
-
Propagation of scc in weld structures of the nickel base alloy 182
-
NACE
-
L.G. Ljungberg, M. Stigenberg, J.L. Nelson, K. Gott, B. Bengtsson, U. Morin, and C. Jansson, "Propagation of SCC in Weld Structures of the Nickel Base Alloy 182", Proc. Int. Symp. on Plant Aging and Life Prediction of Corrodible Structures, NACE, 1995.
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(1995)
Proc. Int. Symp. on Plant Aging and Life Prediction of Corrodible Structures
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Ljungberg, L.G.1
Stigenberg, M.2
Nelson, J.L.3
Gott, K.4
Bengtsson, B.5
Morin, U.6
Jansson, C.7
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42
-
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0004136868
-
Technical report on material selection and processing guidelines for bwr coolant pressure boundary piping
-
U.S. Nuclear Regulatory Commission
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W.S. Hazelton, "Technical Report on Material Selection and Processing Guidelines for BWR Coolant Pressure Boundary Piping", Draft Report NUREGO313, Rev. 2, U.S. Nuclear Regulatory Commission.
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Draft Report NUREGO313, Rev 2
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Hazelton, W.S.1
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43
-
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84911637168
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Modeling of creviced alloy 600 shroud head bolt scc field experience
-
NACE November
-
K.S. Brown, P.L. Andresen and G.M. Gordon, "Modeling of Creviced Alloy 600 Shroud Head Bolt SCC Field Experience", Life Prediction of Corrodible Structures, Hawaii, November 1991, NACE.
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(1991)
Life Prediction of Corrodible Structures, Hawaii
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Brown, K.S.1
Andresen, P.L.2
Gordon, G.M.3
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44
-
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84902567090
-
-
ICONE-4, ASME
-
Peter L. Andresen, F. Peter Ford J. Patrick Higgins, Isao Suzuki, Masakuni Koyama, Mamoru Akiyama, Tadatsune Okubo, Yoshitsugu Mishima, "Life Prediction Of Boiling Water Reactor Internals", ICONE-4, ASME, 1996.
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(1996)
Life Prediction of Boiling Water Reactor Internals
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Andresen, P.L.1
Ford, F.P.2
Higgins, J.P.3
Suzuki, I.4
Koyama, M.5
Akiyama, M.6
Okubo, T.7
Mishima, Y.8
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45
-
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0003475397
-
Computer Calculated Potential pH Diagrams to 300°C
-
June
-
CM. Chen, K. Aral and G.J. Theus, "Computer Calculated Potential pH Diagrams to 300°C, " EPRI NP-3137 Vol.2 (1167-2), June 1983.
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(1983)
EPRI NP-3137
, vol.2
, Issue.1162-1167
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Chen, C.M.1
Aral, K.2
Theus, G.J.3
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